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Method for recovering plutonium from strong acid waste liquid

A technology of waste liquid and strong acid, applied in the direction of improving process efficiency, can solve the problems of large radioactive sludge deposition, difficulty, volume reduction treatment improvement, etc., and achieve fast and efficient decontamination effect, excellent selective quantitative carrying capacity. Effect

Active Publication Date: 2022-08-05
63653 FORCES PLA
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  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0004] Usually, co-precipitation methods such as ferric hydroxide are generally used for decontamination of plutonium in the aqueous phase. However, most of the above methods require co-precipitation reactions in neutral or weakly acidic solution environments. For plutonium waste liquid, the pH should be greatly increased during treatment, and a large amount of alkaline agent needs to be consumed, resulting in a large amount of radioactive sludge deposition; on the other hand, due to the Fe(OH) 3 Precipitation will carry some multivalent ions (Mn, etc.) and actinides (U, etc.), which increases the difficulty for subsequent volume reduction treatment

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  • Method for recovering plutonium from strong acid waste liquid
  • Method for recovering plutonium from strong acid waste liquid
  • Method for recovering plutonium from strong acid waste liquid

Examples

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Effect test

Embodiment 1

[0029] Recovery of plutonium from strong acid waste liquid includes the following steps:

[0030] (1) dissolving neodymium trioxide in 8M nitric acid to prepare a 0.11M neodymium nitrate solution as a carrier solution;

[0031] (2) get the plutonium-containing waste liquid with nitric acid concentration of 4M, after pre-analysis by liquid scintillation, add the neodymium nitrate carrier solution prepared in step (1) according to the atomic molar ratio of different neodymium and plutonium; Fluoride precipitates the carrier, so add 0.5mol / L NH 2 OH·HCl solution, heated at 50°C for 20min, to reduce the hexavalent plutonium in the waste liquid to a low valence state; continue to add 0.5M hydrofluoric acid solution dropwise, slowly add, stir and mix, and leave for 20min, wherein the amount of hydrofluoric acid is based on The total amount of neodymium ions in the solution is calculated, so that all precipitations are appropriately excessive;

[0032] (3) centrifuging the obtained...

Embodiment 2

[0039] Recovery of plutonium from strong acid waste liquid includes the following steps:

[0040] (1) dissolving neodymium trioxide in 8M nitric acid to prepare a 0.11M neodymium nitrate solution as a carrier solution;

[0041] (2) get the plutonium-containing waste liquid with nitric acid concentration of 4M, after pre-analysis by liquid scintillation, add the neodymium nitrate carrier solution prepared in step (1) according to the atomic molar ratio of neodymium and plutonium as 200:1; then add 0.5 M's NH 2 OH·HCl solution, heated at 50℃ for 20min to reduce the hexavalent plutonium in the waste liquid;

[0042] (3) Slowly add 0.5M hydrofluoric acid to the pretreated waste liquid in step (2), and take the supernatant liquid for analysis during the formation of neodymium fluoride precipitation. Since neodymium is pink in the aqueous solution, neodymium in the solution The concentration and absorbance follow Lambert Beer's law, the concentration of neodymium in the solution i...

Embodiment 3

[0049] (1) dissolving neodymium trioxide in 8M nitric acid to prepare a 0.1M neodymium nitrate solution as a carrier solution;

[0050] (2) get the plutonium-containing waste liquid with nitric acid concentration of 8M, after pre-analysis by liquid scintillation, add the neodymium nitrate carrier solution prepared in step (1) according to the atomic molar ratio of neodymium and plutonium as 200:1; then add 0.5 M's NH 2 The OH·HCl solution is heated and reduced to remove the hexavalent plutonium in the solution;

[0051] (3) Slowly add 0.5M hydrofluoric acid under stirring to the pretreated waste liquid in step (2), the amount of hydrofluoric acid added can make 2% of the carrier agent precipitate after calculation, and the generated carrier precipitate is filtered After separation, this step was repeated, and the two partial precipitates were washed with 5% hydrofluoric acid and then collected and dried.

[0052] (4) add 30mL 4M nitric acid solution and 1g boric acid to the ...

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Abstract

The invention discloses a method for recovering plutonium from strong acid waste liquid, and belongs to the technical field of radioactive waste liquid treatment.The method comprises the following steps that 1, a lanthanide series metal ion solution is added into the plutonium-containing strong acid waste liquid, then a precipitant is added for precipitation, the obtained precipitate is collected and dissolved, and a dissolved solution is obtained; (2) adding an oxidizing agent into the dissolved solution obtained in the step (1) to adjust the valence state of the plutonium, and then adding a precipitating agent to remove lanthanide metal ions in the dissolved solution to obtain the plutonium; according to the invention, lanthanide series metal ions are used as a carrier agent, so that the carrier agent has good selective quantitative carrier capacity on plutonium, and shows a rapid and efficient decontamination effect; the method is used for recovering plutonium in the strong acid solution, the reagent dosage is small, secondary products are few, the volume reduction rate of waste is high, the removal rate and recovery rate of plutonium are high, recycling of the carrier agent can be achieved, and the treatment cost is remarkably reduced.

Description

technical field [0001] The invention belongs to the technical field of radioactive waste liquid treatment, and in particular relates to a method for recovering plutonium from strong acid waste liquid. Background technique [0002] Plutonium has a long isotope half-life and high toxicity, and can stably occur in soil media through adsorption, ion exchange, complexation and other effects. The environmental pollution control of plutonium-containing sandy soil is a long-term and huge project, which not only needs to separate plutonium from the soil, but also needs to consider subsequent recovery and disposal. The chemical leaching and decontamination technology transfers plutonium pollutants from the sand solid phase to the leaching liquid phase with the help of various eluents. In order to destroy the chemical binding effect of plutonium in the sandy soil and achieve the exemption target of the plutonium content in the residue after decontamination of the sandy soil being less...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): C22B60/04C22B3/44
CPCC22B60/04C22B3/44Y02P10/20
Inventor 龚荣张晶晶张林沈忠徐辉孟斌洋陈雅琦
Owner 63653 FORCES PLA
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